ML20050D977
| ML20050D977 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/16/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050D980 | List: |
| References | |
| NUDOCS 8204120448 | |
| Download: ML20050D977 (5) | |
Text
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o, UNITED STATES NUCLEAR REGULATORY COMMISSION g
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WASHINGTON. D. C. 20555
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
g.
A.
The applicaticn for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated November 9,1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of 'this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
s 8204120440 820316 PDR ADOCK 05000334 P
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Accordingly, the if cense is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices l
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A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
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l FD THE NUCLEAR FQLATORY COMISSION 3
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ga, Chi Operating Reactors B a ch #1 Division of Licensin
Attachment:
Changes to the Technical Specifications,
t Date of Issuance: March 16,1982 l
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 4-8 3/4 4-8 3/4 4-29 3/4 4-29 9
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STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable above 200*F.
generator (s) to OPERABLE status prior to increasing T,yg SURVEILLANCE REQUIREMENTS Steam Generator Sample Selection and Inspection - Each steam 4.4.5.1 generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
Steam Generator Tube Sample Selection and Inspection - The steam 4.4.5.2 generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Steam generator tubes shall be examined in Specification 4,4.5.4.
accordance with the method prescribed in Article 8
" Eddy Current Examination of Tubular Products," as contained in ASME Boiler and Pressure Vessel Code,Section V "Non-destructive Examination," and referenced in ASME Boiler and Pressure Vessel Code - Appendix IV of the 1980 Edition through Winter 1980 Addenda of Section XI -
" Inservice Inspection of Nuclear Power Plant Components." The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water a.
chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously bad detectable wall penetrations (>20%), and 2.
Tubes in those areas where experience has indicated potential problems.
f BEAVER VALLEY - UNIT 1 3/4 4-8 Amendment No. 48 l
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N REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) a.
At the first refueling outage, dye penetrant inspections shall t
be performed on all stx reactor vessel nozzles and volumetric inspections shall be performed on at least two nozzles in the same manner as that conducted in the baseline inspection.
b.
At the second refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultra-sonic examination shall be performed on all six nozzle to safe end welds from the outside diameter.
At the third refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultra-sonic examination shall be performed on all six nozzle to safe end welds from the outside diameter. Ultrasonic examination shall be performed on the three outlet nozzle to safe end welds from the inside diameter.
c.
Defects found during these inspections shall be evaluated to determine their significance and reported to the Commission pursuant to Technical Specification 6.9.1.8.c.
BEAVER VALLEY - UNIT 1 3/4 4-29 Anendment No. ff 48
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